Notice of Issuance of Regulatory Guide, 9626-9627 [2010-4435]
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Federal Register / Vol. 75, No. 41 / Wednesday, March 3, 2010 / Notices
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request from March 31, 2010, to June 30,
2011, for five specific requirements of
the new rule. As stated above, 10 CFR
73.5 allows the NRC to grant
exemptions from the requirements of 10
CFR part 73. The NRC staff has
determined that granting of the
licensee’s proposed exemption would
not result in a violation of the Atomic
Energy Act of 1954, as amended, or the
Commission’s regulations. Therefore,
the exemption is authorized by law.
In the draft final rule provided to the
Commission on July 9, 2008, the NRC
staff proposed that the requirements of
the new regulation be met within 180
days. The Commission directed a
change from 180 days to approximately
1 year for licensees to fully implement
the new requirements. This change was
incorporated into the final rule. From
this, it is clear that the Commission
wanted to provide a reasonable
timeframe for licensees to achieve full
compliance.
As noted in the final Power Reactor
Security Requirements rule (74 FR
13925, March 27, 2009), the
Commission also anticipated that
licensees would have to conduct site
specific analyses to determine what
changes were necessary to implement
the rule’s requirements, and that these
changes could be accomplished through
a variety of licensing mechanisms,
including exemptions. Since issuance of
the final rule, the Commission has
rejected a generic industry request to
extend the rule’s compliance date for all
operating nuclear power plants, but
noted that the Commission’s regulations
provide mechanisms for individual
licensees, with good cause, to apply for
relief from the compliance date
(Reference: June 4, 2009 letter from R.
W. Borchardt, NRC, to M.S. Fertel,
Nuclear Energy Institute). The licensee’s
request for an exemption is therefore
consistent with the approach set forth
by the Commission and discussed in the
June 4, 2009, letter.
PINGP Schedule Exemption Request
The licensee provided detailed
information in Enclosures 1 and 2 of its
November 5, 2009, submittal letter
requesting an exemption, as well as in
its supplemental letter dated December
17, 2009. It describes a comprehensive
plan to upgrade the security capabilities
of the PINGP site and provides a
timeline for achieving full compliance
with the new regulation. Enclosures 1
and 2 contain security-related
information regarding the site security
plan, details of specific portions of the
regulation for which the site cannot be
in compliance by the March 31, 2010,
deadline and why, the required changes
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16:08 Mar 02, 2010
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to the site’s security configuration, and
a timeline with critical path activities
that will bring the licensee into full
compliance by June 30, 2011. The
licensee stated that the schedule for the
physical modifications associated with
this request were developed based on
current information and anticipated
impediments to construction such as
planned refueling outages at both Units
1 and 2 and winter weather conditions
that may impair construction due to
frozen ground or extreme cold that
creates personnel safety issues.
Enclosure 2 to the November 5, 2009,
submittal includes a timeline that
provides dates indicating when (1)
construction will begin on various
phases of the project, (2) outages are
scheduled for each unit, and (3) critical
equipment will be ordered, installed,
and become operational.
Notwithstanding the schedular
exemptions for these limited
requirements, the licensee will continue
to be in compliance with all other
applicable physical security
requirements as described in 10 CFR
73.55 and reflected in its current NRC
approved physical security program. By
June 30, 2011, PINGP will be in full
compliance with all the regulatory
requirements of 10 CFR 73.55, as issued
on March 27, 2009.
4.0 Conclusion for Part 73 Schedule
Exemption Request
The staff has reviewed the licensee’s
submittals and concludes that the
licensee has provided adequate
justification for its request for an
exemption from the March 31, 2010,
compliance date to June 30, 2011, with
regard to the specified requirements of
10 CFR 73.55.
Accordingly, the Commission has
determined that pursuant to 10 CFR
73.5, ‘‘Specific exemptions,’’ exemption
from the March 31, 2010, compliance
date is authorized by law and will not
endanger life or property or the common
defense and security, and is otherwise
in the public interest. Therefore, the
Commission hereby grants the requested
exemption.
The NRC staff has determined that the
long-term benefits that will be realized
when these projects are complete justify
extending the March 31, 2010, full
compliance date with regard to the
specified requirements of 10 CFR 73.55
for this particular licensee. The security
measures, that PINGP needs additional
time to implement, are new
requirements imposed by March 27,
2009 amendments to 10 CFR 73.55, and
are in addition to those required by the
security orders issued in response to the
events of September 11, 2001.
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Therefore, it is concluded that the
licensee’s actions are in the best interest
of protecting the public health and
safety through the security changes that
will result from granting this exemption.
As per the licensee’s request and the
NRC’s regulatory authority to grant an
exemption from the March 31, 2010,
compliance date for the five
requirements specified in Enclosure 1 of
the NSPM letter dated November 5,
2009, the licensee is required to be in
full compliance by June 30, 2011. In
achieving compliance, the licensee is
reminded that it is responsible for
determining the appropriate licensing
mechanism (i.e., 10 CFR 50.54(p) or 10
CFR 50.90) for incorporation of all
necessary changes to its security plans.
Pursuant to 10 CFR 51.32, ‘‘Finding of
no significant impact,’’ the Commission
has previously determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment [75 FR 6225; dated
February 8, 2010].
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 23rd day
of February 2010.
For The Nuclear Regulatory Commission.
Allen G. Howe,
Acting Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2010–4382 Filed 3–2–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2008–0577]
Notice of Issuance of Regulatory Guide
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of issuance and
availability of Regulatory Guide 1.47,
Revision 1, ‘‘Bypassed and Inoperable
Status Indication for Nuclear Power
Plant Safety Systems.’’
FOR FURTHER INFORMATION CONTACT:
Khoi Nguyen, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 251–7453 or email Khoi.Nguyen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revision
to an existing guide in the agency’s
‘‘Regulatory Guide’’ series. This series
was developed to describe and make
available to the public information such
as methods that are acceptable to the
E:\FR\FM\03MRN1.SGM
03MRN1
mstockstill on DSKH9S0YB1PROD with NOTICES
Federal Register / Vol. 75, No. 41 / Wednesday, March 3, 2010 / Notices
NRC staff for implementing specific
parts of the agency’s regulations,
techniques that the staff uses in
evaluating specific problems or
postulated accidents, and data that the
staff needs in its review of applications
for permits and licenses.
Revision 1 of Regulatory Guide 1.47
was issued with a temporary
identification as Draft Regulatory Guide,
DG–1205. This guide describes a
method that the staff of the NRC
considers acceptable for use in
complying with the NRC’s regulations
with respect to bypassed and inoperable
status indication for nuclear power
plant safety systems.
The regulatory framework that the
NRC has established for nuclear power
plants consists of a number of
regulations and supporting guidelines
applicable to bypassed and inoperable
status indication, including, but not
limited to, General Design Criterion
(GDC) 1, ‘‘Quality Standards and
Records,’’ GDC 13, ‘‘Instrumentation and
Control,’’ GDC 19, ‘‘Control Room,’’ GDC
21, ‘‘Protection System Reliability and
Testability,’’ GDC 22, ‘‘Protection System
Independence,’’ and GDC 24,
‘‘Separation of Protection and Control
Systems,’’ as set forth in Appendix A,
‘‘General Design Criteria for Nuclear
Power Plants,’’ to Title 10, Part 50,
‘‘Domestic Licensing of Production and
Utilization Facilities,’’ of the Code of
Federal Regulations (10 CFR part 50).
GDC 1 requires that structures, systems,
and components important to safety be
designed and installed to quality
standards commensurate with the
importance-to-safety of the functions to
be performed. GDC 13 requires that
appropriate controls be provided to
maintain variables and systems that can
affect the fission process, the integrity of
the reactor core, the reactor coolant
pressure boundary, and the containment
and its associated systems within
prescribed operating ranges. GDC 19
requires that a control room be provided
from which actions can be taken to
operate the nuclear power unit safely
under normal operating conditions.
GDC 21 requires that the protection
system be designed for high functional
reliability and inservice testability. GDC
22 requires that the protection system be
designed to ensure that the effects of
normal operating, maintenance, and
testing on redundant channels do not
result in the loss of the protection
function or be demonstrated to be
acceptable on some other defined basis.
GDC 24 requires that interconnection of
the protection and control systems be
limited to ensure that safety is not
significantly impaired.
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16:08 Mar 02, 2010
Jkt 220001
II. Further Information
In October 2008, DG–1205 was
published with a public comment
period of 60 days from the issuance of
the guide. The public comment period
closed on December 22, 2008. The staff’s
responses to the comments received are
located in the NRC’s Agencywide
Documents Access and Management
System (ADAMS) under Accession No.
ML092330085.
Electronic copies of Regulatory Guide
1.47, Revision 1 are available through
the NRC’s public Web site under
‘‘Regulatory Guides’’ at https://
www.nrc.gov/reading-rm/doccollections/.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR) located at
Room O–1F21, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852–2738. The PDR’s
mailing address is USNRC PDR,
Washington, DC 20555–0001. The PDR
can also be reached by telephone at
(301) 415–4737 or (800) 397–4209, by
fax at (301) 415–3548, and by e-mail to
pdr.resource@nrc.gov.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
Dated at Rockville, Maryland, this 24th day
of February 2010.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. 2010–4435 Filed 3–2–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0384]
Notice of Issuance of Regulatory Guide
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of issuance and
availability of Regulatory Guide 1.40.
FOR FURTHER INFORMATION CONTACT:
Thomas Koshy, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: (301) 251–7663, e-mail:
Thomas.Koshy@nrc.gov, or R.A. Jervey,
telephone: (301) 251–7404, e-mail:
Richard.Jervey@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revision
to an existing guide in the agency’s
‘‘Regulatory Guide’’ series. This series
PO 00000
Frm 00056
Fmt 4703
Sfmt 4703
9627
was developed to describe and make
available to the public information such
as methods that are acceptable to the
NRC staff for implementing specific
parts of the agency’s regulations,
techniques that the staff uses in
evaluating specific problems or
postulated accidents, and data that the
staff needs in its review of applications
for permits and licenses.
Revision 1 of Regulatory Guide 1.40,
‘‘Qualification of Continuous Duty
Safety-Related Motors for Nuclear
Power Plants,’’ was issued with a
temporary identification as Draft
Regulatory Guide DG–1150.
This RG describes a method that the
staff of the NRC deems acceptable for
complying with the Commission’s
regulations for qualification of
continuous duty safety-related motors
for nuclear power plants.
The Commission’s regulations in Title
10, Part 50, ‘‘Domestic Licensing of
Production and Utilization Facilities,’’ of
the Code of Federal Regulations (10 CFR
part 50), require that structures,
systems, and components in a nuclear
power plant that are important to safety
be designed to accommodate the effects
of environmental conditions (i.e., they
must remain functional under
postulated design-basis events). Toward
that end, General Design Criteria 1, 2, 4,
and 23 of Appendix A, ‘‘General Design
Criteria for Nuclear Power Plants,’’ to
10 CFR Part 50 contain the general
requirements. The specific requirements
pertaining to qualification of certain
electrical equipment important to safety
appear in 10 CFR 50.49, ‘‘Environmental
Qualification of Electric Equipment
Important to Safety for Nuclear Power
Plants.’’ In addition, Criterion III,
‘‘Design Control,’’ of Appendix B,
‘‘Quality Assurance Criteria for Nuclear
Power Plants and Fuel Reprocessing
Plants,’’ to 10 CFR part 50, requires that
test programs, when used to verify the
adequacy of a specific design feature,
should include suitable qualification
testing of a prototype unit under the
most adverse design conditions.
II. Further Information
In August 2009, DG–1150 was
published with a public comment
period of 60 days from the issuance of
the guide. The public comment period
closed on October 30, 2009. The staff’s
responses to the comments received are
located in the NRC’s Agencywide
Documents Access and Management
System under accession number
ML093080126. Electronic copies of RG
1.40, Revision 1 are available through
the NRC’s public Web site under
‘‘Regulatory Guides’’ at https://
E:\FR\FM\03MRN1.SGM
03MRN1
Agencies
[Federal Register Volume 75, Number 41 (Wednesday, March 3, 2010)]
[Notices]
[Pages 9626-9627]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-4435]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2008-0577]
Notice of Issuance of Regulatory Guide
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of issuance and availability of Regulatory Guide 1.47,
Revision 1, ``Bypassed and Inoperable Status Indication for Nuclear
Power Plant Safety Systems.''
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Khoi Nguyen, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, telephone (301) 251-7453 or e-
mail Khoi.Nguyen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision
to an existing guide in the agency's ``Regulatory Guide'' series. This
series was developed to describe and make available to the public
information such as methods that are acceptable to the
[[Page 9627]]
NRC staff for implementing specific parts of the agency's regulations,
techniques that the staff uses in evaluating specific problems or
postulated accidents, and data that the staff needs in its review of
applications for permits and licenses.
Revision 1 of Regulatory Guide 1.47 was issued with a temporary
identification as Draft Regulatory Guide, DG-1205. This guide describes
a method that the staff of the NRC considers acceptable for use in
complying with the NRC's regulations with respect to bypassed and
inoperable status indication for nuclear power plant safety systems.
The regulatory framework that the NRC has established for nuclear
power plants consists of a number of regulations and supporting
guidelines applicable to bypassed and inoperable status indication,
including, but not limited to, General Design Criterion (GDC) 1,
``Quality Standards and Records,'' GDC 13, ``Instrumentation and
Control,'' GDC 19, ``Control Room,'' GDC 21, ``Protection System
Reliability and Testability,'' GDC 22, ``Protection System
Independence,'' and GDC 24, ``Separation of Protection and Control
Systems,'' as set forth in Appendix A, ``General Design Criteria for
Nuclear Power Plants,'' to Title 10, Part 50, ``Domestic Licensing of
Production and Utilization Facilities,'' of the Code of Federal
Regulations (10 CFR part 50). GDC 1 requires that structures, systems,
and components important to safety be designed and installed to quality
standards commensurate with the importance-to-safety of the functions
to be performed. GDC 13 requires that appropriate controls be provided
to maintain variables and systems that can affect the fission process,
the integrity of the reactor core, the reactor coolant pressure
boundary, and the containment and its associated systems within
prescribed operating ranges. GDC 19 requires that a control room be
provided from which actions can be taken to operate the nuclear power
unit safely under normal operating conditions. GDC 21 requires that the
protection system be designed for high functional reliability and
inservice testability. GDC 22 requires that the protection system be
designed to ensure that the effects of normal operating, maintenance,
and testing on redundant channels do not result in the loss of the
protection function or be demonstrated to be acceptable on some other
defined basis. GDC 24 requires that interconnection of the protection
and control systems be limited to ensure that safety is not
significantly impaired.
II. Further Information
In October 2008, DG-1205 was published with a public comment period
of 60 days from the issuance of the guide. The public comment period
closed on December 22, 2008. The staff's responses to the comments
received are located in the NRC's Agencywide Documents Access and
Management System (ADAMS) under Accession No. ML092330085.
Electronic copies of Regulatory Guide 1.47, Revision 1 are
available through the NRC's public Web site under ``Regulatory Guides''
at https://www.nrc.gov/reading-rm/doc-collections/.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR) located at Room O-1F21, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-2738. The
PDR's mailing address is USNRC PDR, Washington, DC 20555-0001. The PDR
can also be reached by telephone at (301) 415-4737 or (800) 397-4209,
by fax at (301) 415-3548, and by e-mail to pdr.resource@nrc.gov.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
Dated at Rockville, Maryland, this 24th day of February 2010.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. 2010-4435 Filed 3-2-10; 8:45 am]
BILLING CODE 7590-01-P